Alcator C-Mod experiments in support of the ITER baseline 15 MA scenario

被引:11
作者
Kessel, C. E. [1 ]
Wolfe, S. M. [2 ]
Hutchinson, I. H. [2 ]
Hughes, J. W. [2 ]
Lin, Y. [2 ]
Ma, Y. [2 ]
Mikkelsen, D. R. [1 ]
Poli, F. M. [1 ]
Reinke, M. L. [2 ]
Wukitch, S. J. [2 ]
机构
[1] Princeton Plasma Phys Lab, Princeton, NJ 08543 USA
[2] MIT, Plasma Sci & Fus Ctr, Cambridge, MA 02139 USA
关键词
PLASMA; CONSUMPTION; DENSITY; LIMITS; JET;
D O I
10.1088/0029-5515/53/9/093021
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
Experiments on Alcator C-Mod from 2009-2012 have examined the rampup, flattop and rampdown phases of the proposed ITER 15 MA baseline scenario. Rampup studies show ICRF heating can significantly reduce the V-s requirement, and that an H-mode late in the ramp can reduce this further. ICRF modifications to l(i) in L-mode are minimal, although the T-e profile is peaked relative to ohmic in the plasma centre, and reduces the sawtooth onset times. Flattop plasmas targeting ITER baseline parameters have been sustained for 20 tau(E) or 8 - 13 tau(CR), but only reach H-98 similar to 0.6 at n/n(Gr) = 0.85, rising to 0.9 at n/n(Gr) = 0.65. Rampdown studies show H-modes can be routinely sustained with ICRF power injection, avoiding an OH coil over-current associated with the H-L transition. In addition, faster current rampdowns are preferred to avoid an over-current when an H-L transition ultimately does occur. In the H-mode rampdown the density is found to drop with I-p, preserving the n/n(Gr) ratio, so long as ICRF power is injected.
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页数:12
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